last modified: 01-FEB-1979 | catalog | categories | new | search |

NEA-0499 HYDY-B1.

HYDY-B1, Channel Thermohydraulics During LOCA of BWR, PWR

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1. NAME OR DESIGNATION OF PROGRAM:  HYDY-B1.
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2. COMPUTERS
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Program name Package id Status Status date
HYDY-B1 NEA-0499/01 Tested 01-FEB-1979

Machines used:

Package ID Orig. computer Test computer
NEA-0499/01 IBM 370 series IBM 370 series
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3. NATURE OF PHYSICAL PROBLEM SOLVED

Thermo-hydraulic response of reactor channel(s) during the decompression phases of loss-of-coolant accidents (LOCA) is solved. The code may be applicable not only to BWR's, but also to PWR's.
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4. METHOD OF SOLUTION

The one-dimensional heat conduction equation for a single rod and the one-dimensional equations of conservation of mass, energy and momentum are cast into difference equations and then are solved by explicit integration. Main inputs to the code are the temporal variations of mass flow rate, average specific enthalpy and pressure at the channel inlet.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:  One-dimensional
channel flow with one or two fuel rods.
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6. TYPICAL RUNNING TIME

700 seconds for 35 seconds (physical time) calculation with 14 coolant nodes and 96 fuel nodes.
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7. UNUSUAL FEATURES OF THE PROGRAM

Time step automatically changes as the calculation proceeds.
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8. RELATED OR AUXILIARY PROGRAMS: RELATED AND AUXILIARY PROGRAMS
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9. STATUS
Package ID Status date Status
NEA-0499/01 01-FEB-1979 Tested at NEADB
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10. REFERENCES

- "Safety Evaluation Guide Line for Emergency Core Cooling Systems
   of Light Water Cooled Nuclear Power Reactors"
   Committee on Reactor Safety Examination
   Japanese Atomic Energy Commission
   May 24, 1974. April 15, 1975 (rev. 1). In Japanese.
- N. Zuber and F.W. Staub:
  Nucl. Sci. Eng. 30, 268 (1967).
- R.B. Bird, W. Stewart and E.N. Lightfoot:
  "Transport Phenomena"
  John Wiley and Sons, Inc., New York (1960).
- K. Shure:
  "Fission Product Decay Energy"
  Report WAPD-BT-24 , Westinghouse Atomic Power Division, (1961).
- Proposed American Nuclear Society Standard:
  "Decay Energy Release Rates Following Shutdown of Uranium-Fueled
   Thermal Reactors"
  Approved by Subcommittee ANS-5, ANS Standard Committee
  (October 1971, Revised October 1973).
- H. Blasius:
  Forsch. Arb. Wes., Nr. 131 (1924).
- H.C. Hottel:
  "Radiation Heat Transmission"
   Chapter 4 of "Heat Transmission" by W.H. McAdams McGraw-Hill
   (1954).
- M. Jacob:
  "Heat Transfer", vol. 1
  New York, Wiley and Sons (1957).
- W.H. Jens and P. Lottes:
  "Analysis of Heat Transfer, Burnout, Pressure Drop and Density
   Data for High-Pressure Water"
  ANL-4627 (1951).
- D.C. Groeneveld:
"An Investigation of Heat Transfer in the Liquid Deficient Regime"    AECL-3281 (rev.) (December 1968. Revised August 1969).
- D.M. McEligot, L.W. Ormand and H.C. Perkins, Jr.:
  Trans. Amer. Soc. Mech. Engrs., 88, Series C, p. 239-245 (May
  1966).
- B.C. Slifer and J.E. Hench:
"Loss-of-Coolant Accident and Emergency Cooling Models for General     Electric Boiling Water Reactors"
  NEDO-10329 General Electric Company, Equation C-32 (April 1971).
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11. HARDWARE REQUIREMENTS: MACHINE REQUIREMENTS
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0499/01 FORTRAN-IV
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13. SOFTWARE REQUIREMENTS: OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
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15. NAME AND ESTABLISHMENT OF AUTHOR

     Y. Asahi
     Tokai Research Establishment
     Japan Atomic Energy Research Institute
     Tokai-Mura, Naka-Gun, Ibaraki-Ken
     Japan
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16. MATERIAL AVAILABLE
NEA-0499/01
File name File description Records
NEA0499_01.001 SOURCE PROGRAM (F4,EBCDIC) 5728
NEA0499_01.002 SAMPLE PROBLEM INPUT DATA 51
NEA0499_01.003 SAMPLE PROBLEM PRINTED OUTPUT 1191
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: BWR reactors, heat transfer, hydraulics, loss-of-coolant accident, one-dimensional, pwr reactors, reactor channels, reactor safety, thermodynamics.